EP0799485B1 - Kühlsystem zur kühlung eines zur aufnahme von kernschmelze ausgelegten rückhalteraums - Google Patents
Kühlsystem zur kühlung eines zur aufnahme von kernschmelze ausgelegten rückhalteraums Download PDFInfo
- Publication number
- EP0799485B1 EP0799485B1 EP95943159A EP95943159A EP0799485B1 EP 0799485 B1 EP0799485 B1 EP 0799485B1 EP 95943159 A EP95943159 A EP 95943159A EP 95943159 A EP95943159 A EP 95943159A EP 0799485 B1 EP0799485 B1 EP 0799485B1
- Authority
- EP
- European Patent Office
- Prior art keywords
- cooling
- flood
- conduit
- closure element
- cooling system
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Lifetime
Links
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/016—Core catchers
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Definitions
- the invention relates to a cooling system with a cooling line and / or a flood line for cooling a containment room to absorb meltdown of a reactor core of a nuclear power plant.
- Nuclear power plants have a variety for safe operation diverse and redundant security systems, including Cooling systems on, by early on from normal operating conditions deviating operating conditions are recognized and these can be counteracted. Safety-critical conditions, such as melting the core of the reactor, are practically excluded.
- the core restraint has a collecting container, which is immediately below the arranged the reactor core including the reactor pressure vessel is.
- the collecting tank as well as the reactor pressure tank are formed within a concrete structure Reactor cavern arranged. Between the collecting container and Concrete structures run on the floor and on the walls of the collecting container Cooling channels through which cooling water can be passed.
- the cooling channels on the bottom are connected to a water supply and open into a cooling line, which is siphon-like in protrudes the water supply.
- the siphon-like cooling line has a part with an upside down U, where the apex of the U's is above an operational Level of the water supply and the cooling line immersed in the water supply, but in the vicinity of the Vertex protrudes from the water supply.
- no cooling water reaches during the operational water level into the cooling channels. Only when the water supply is flooded to a level that exceeds the U's apex, cooling water gets into the cooling channels and it takes place cooling of the collecting container on its outside.
- the interior of the collecting container is cooled via a flood pipe leading from the water supply through the concrete structure is led into the collecting container.
- the flood line is in the container by a meltable Plug closed, which only at a high ambient temperature melts, causing cooling water to enter the interior of the collecting container can flow in. In the flood line even during normal operation of the nuclear power plant cooling water available, which means that the meltable stopper is constantly on is cooled.
- the object of the invention is a cooling system for cooling a designed to hold meltdown in the retention room to indicate which is inherently by passive means and thus safely initiates cooling of the collecting container.
- the object is achieved by a cooling system of the type specified in claim 1 solved.
- Cooling fluid is preferably primary cooling water, which during the safety-critical state from the primary cooling circuit of the reactor core emerges. Cooling fluid can if necessary via a separate cooling fluid reservoir in the Flood tanks are fed. Until the closure element is opened the cooling line / flood line is closed and thus free of water. This is during normal operation the nuclear power plant cooling fluid, especially cooling water, from kept away from the containment area, which prevents disruptive influences, such as corrosion from cooling water or an unwanted Cooling a temperature-dependent, the cooling line closing closure element is avoided. In addition is inherent through the passively opening closure element Nuclear power plant safety improved, being human Failure to initiate cooling of the containment room is excluded.
- the closure element is a closing the cooling line / flood line Floating body.
- This float features an operational level of the cooling water via a such buoyancy that it, for example, the cooling line / flood line seals a valve ball seat.
- the floating body is preferably movable in a guide along a main axis, so that the float slips unintentionally from its sealing seat even in the event of vibrations, which for example caused by earthquakes, is avoided.
- the floating body preferably has one that can be filled with cooling fluid Inner space.
- a filling pipe is inserted into this interior, which has an inlet opening for cooling fluid, through that at a geodetically above an operational water level lying flooded level coolant flows in.
- the inlet opening can be geodetically above the operational Level or geodetically below this operational level Level are, in the latter case the fill pipe from the inlet opening U-shaped over the operational Level is led out, so that an apex of the U's upside down above the operational water level lies. In the latter case, too, flows only when exceeded the operational level by a predeterminable Measure cooling fluid into the interior of the float.
- In the Interior cooling fluid reduces the buoyancy of the floating body, so that this from a certain Degree of filling of the interior leaves its sealing seat and thereby the cooling line is opened. Cooling of the containment room hereby uses in a passive way.
- the floating body preferably has a led into the interior Condensation drainage, through which during a normal operating condition of the nuclear power plant Condensed water can be sucked out. This is a sinking of the float due to condensation and thereby an unwanted initiation of cooling of the retention area safely avoided.
- the retention space is preferably with the flood tank one geodetically above the cooling line, especially above of the operational water level, ongoing feedback for cooling fluid, which in the flood tank with a closed further locking element depending on the level is.
- ongoing feedback for cooling fluid which in the flood tank with a closed further locking element depending on the level is.
- the retention space is reached through a cooling fluid circuit, wherein flowing from the flood tank to the retention space Cooling fluid flows in a natural circulation.
- the closure element which is the return in the flood tank closes and can also be a floating body, preferably has a ball valve.
- This ball valve can floatable ball, which with a guideway in a Sealed position is maintained.
- the ball valve protects the closure element against a pressure wave, which for example by increasing the temperature inside of the retention space can occur.
- the cooling line is preferably a flood line, which in the retention space opens and thereby direct cooling, especially the surface, one that has flowed into the retention space Meltdown guaranteed.
- the flood line runs preferably horizontal and is from the flood tank can be assembled and disassembled. Installation of the flood line from the flood tank into the retention space has the advantage that the assembly outside of the possibly difficult to access and possibly contaminated containment space. This is particularly the case with one that encloses the reactor core Retention space is particularly cheap because it can be installed after usually provided lining of the retention space with a crucible-like protective and collecting layer can take place.
- the flood line is during normal operation Nuclear power plant in the containment room preferably with a temperature dependent opening closure element closed. She is with during the normal operation of the nuclear power plant Air filled, causing the temperature-dependent opening element thermally compared to the cooling water of the flood tank is isolated and cooling water only during a safety critical Condition of the nuclear power plant in the Flood line arrives, so that corrosion influences are safely avoided are. Due to the thermal insulation of the temperature dependent opening closure element is a safe opening, especially melting, with strong heat development guaranteed within the containment room. The temperature-dependent opening closure element can therefore be designed so that it is in contact with cooling water direct contact closure element only at higher Temperatures the flood line opens.
- the temperature opening closure element is preferably resistant to Neutron radiation, which occurs during normal operation the nuclear power plant in the immediate vicinity of the reactor core, especially in the receiving the reactor pressure vessel Reactor cavern occurs. It also has an advantage only one melting element (melting screw, Enamel band), causing canting and thus delayed Opening the closure element with several too different Melting elements is avoided.
- the Closure element is also the cross section of the flood line adapted so that an assembly of the flood line with already attached closure element is guaranteed.
- the closure element has a temperature-dependent opening one at a high temperature, for example above 900 ° C, melting material.
- This material can corrosion and radiation resistant, especially Silver, be.
- the temperature-dependent opening element can be a clasp with a clamping screw Have silver. The clasp presses a lid sealing into the flood line, so that this during normal Operation of the nuclear power plant locked with security is.
- the temperature-dependent opening element can alternatively have a closure cap which with the Flood line is soldered to seal. As a solder substance, it can if silver serve.
- the retention space preferably has external cooling for the outside Cooling at least one floor and / or wall of the retention space, the cooling line and the external cooling supply line connecting to the flood tank.
- the supply line is during normal operation of the nuclear power plant closed by a floating body.
- the outside cooling preferably has a drain for the cooling fluid, which leads back into the flood tank. This way Cooling fluid, especially that which has flowed into the flood tank Primary cooling water, back into the flood tank so that A cooling circuit for external cooling of the containment room given is.
- the retention space can be a crucible-like one, below the reactor core arranged collection container. Cooling the Collecting container, which is passively operated by a uses floating bodies arranged in the flood tank, is carried out on the outside of the collecting container by the External cooling and / or inside of the collecting container a flood line.
- one is from the flood tank to the catch tank and heat-elastic flowing into the latter guided.
- the flood line has outside the collecting tank, in particular between the wall of the collecting container and one a concrete structure forming a reactor cavern a compensator.
- the especially welded expansion joint with one welded flange in spherical shape seals the collecting container, which, for example, has a temperature inside of approx. 300 ° C compared to the external cooling of the collecting container with a temperature of 20 ° C to 30 ° C.
- the compensator serves to compensate for thermal expansion of the collecting container and also ensures a seal the flood line opposite a cooling fluid flow for cooling the outer wall of the collecting container.
- the cooling system is also suitable for cooling one side Spreading space arranged below the reactor core.
- the expansion area can be which leads from a flood tank into the spreading space, be chilled inside.
- An external cooling the expansion area through corresponding cooling channels, which by a passively opening closure element, for example a float inside the flood tank, flooded with cooling fluid is also possible.
- FIGS. 1 to 5 designate each same components of the embodiment.
- FIG. 1 shows a section of a longitudinal section through a nuclear power plant with a cooling system 1 for cooling a retention space 2 designed to accommodate meltdown.
- a reactor pressure vessel 3 which is largely rotationally symmetrical about its main axis 5 is arranged in a reactor cavern 48 formed by a support structure 36.
- the reactor pressure vessel 3 contains a reactor core 4.
- a retention space 2 is formed in the reactor cavern 48 by a meltdown container 28 which has a bottom 24 and a wall 25. Between the support structure 36 and the wall 25 and the floor 24 there remains a space for external cooling 23 of the collecting container 28.
- a lining 38 for example made of zirconium oxide stones (ZrO 2 ), on.
- a layer of sacrificial concrete 27 is arranged on the bottom lining 38, in particular to lower the melting point of a meltdown.
- a cooling line 6, designed as a flood line 31 for cooling fluid 7, is arranged through the wall 25 and the adjoining support structure 36 with a slight inclination with respect to the horizontal, which leads from a flood tank 8 into the collecting tank 28.
- the flood line 31 is opened by a closure element 15, in particular a temperature-dependent one; of the closure element 15, closed.
- the flood line 31 is closed by a closure element 9 which opens as a function of the level, in particular with a floating body 10.
- the flood line 31 is surrounded by a compensator 29, which seals the wall 25 against the external cooling 23 and absorbs thermal expansion of the collecting container 28.
- the floating body 10 sealing the flood line 31 has an interior 11 into which a filler tube 12 is inserted, which has an inlet opening 13 geodetically above the flood line 31.
- the inlet opening 13 is also above an operational level 14 of the cooling fluid 7, in particular cooling water, which is located in the flood tank 8.
- the external cooling 23 of the collecting container 28 is connected to the flood container 8 by a feed line 26 running essentially horizontally below the reactor cavern 48 through the support structure 36.
- the feed line 26 is also closed by a closure element 9 with a float 10.
- a filling tube 12 protrudes into the interior 11 of the floating body 10, which is led out of the cooling fluid 7 up to the operational level 14 and bent back into the cooling fluid 7 in a U-shape, where it ends in an inlet opening 13.
- this return 20 is through a further closure element 21, with a further floating body 10, which is approximately half is immersed in the cooling water 7, closed.
- a ball valve 22 with a floating ball is arranged between the further closure element 21 and the return 20.
- Each of the closure elements 9, 21 has a respective condensate suction 19.
- the return 20 runs in the reactor cavern 48 above the collecting container 28 through the support structure 36 and through an insulation 37 adjoining the support structure 36.
- the return 20 is connected to the inside of the collecting container 28.
- the external cooling 23, the flood line 31, the return line 20 and the cooling system 1 comprising the closure elements 9, 21, 15 locked.
- the outside cooling 23 is used during normal operation of the nuclear power plant operational air cooling, thereby heating the Support structure is prevented.
- the lie outside the support structure 36 cooling air is after below in the feed line 26, which is designed as an annular channel and connected to eight horizontal channels to which Outside of the receptacle 28 out.
- the warming one Cooling air rises on the outside of the collecting container 28 and the support structure 36 upwards and cannot in that shown reactor buildings of the nuclear power plant escape.
- the ring channel is also over eight pipes with the flood tank 8 connected.
- the additional Cooling fluid is from the primary cooling circuit of the reactor core 4 escaping primary cooling water.
- the additional Cooling fluid can optionally be from a separate additional Cooling fluid supply can be fed.
- the floats 10, which close the flood line 31 and the external cooling 23, are filled with cooling water 7 and sink due to of the decreasing buoyancy. This will both the flood line 31 and the external cooling 23 with Cooling water 7 filled. When exceeding the operational Level 14 first uses the external cooling 23.
- a Cooling water 7 is recirculated via the external cooling 23 over six horizontally running channels, not shown above the operational level 14 in the flood tank 7.
- the return of the external cooling 23 and the return 20 of the internal cooling are separated from each other.
- the due of the melting reactor core 4 emerging meltdown leads to heat development in the collecting container 28, through the closure element, which opens depending on the temperature 15 of the flood line 31 also opens.
- coolant fluid 7 flows into the interior of the collecting container 28 for cooling the meltdown.
- the increased water level within the flood tank 8 then drops to a flood level 32, for example by 30 cm to 60 cm, so that the level of the cooling water 7 in the reactor cavern 48 and the flood tank 8 is the same height.
- cooling fluid 7 flowing in through the flood line 31 warms and rises according to the flow arrows 30 shown in a natural circulation and flows through the return 20 back into the flood tank 8 (through the flow arrows 30 shown).
- External cooling 23 passes through the feed line 26 from the flood tank 8 cooling water 7, as represented by the flow arrows 44, to the outside of the collecting container 28, which evaporated there and via channels not shown in the Flood tank 8 is returned.
- the evaporated cooling water 7 rises within the nuclear power plant condenses and reaches the flood tank 8 back.
- opening closure elements 9 for the flood line 31 and for the external cooling 23 is an effective cooling a meltdown impinging in the collecting container 28 guaranteed over a long period of time.
- the further closure element 21 according to FIG. 1 is included a float 10 and a ball valve 22 with a Floatable ball shown on an enlarged scale.
- Float 10 is at an operational water level 14 about half immersed in the cooling water 7.
- the Floatable ball of the ball valve 22 rests on one of the return 20 to the floating body 10 falling Ball position holder 33. Even with one in the reactor cavern 48 arising and about the return 20 propagating pressure wave seals the ball valve 22 Floating body 10, whereby it remains protected.
- the ball valve 22 has a vent 34.
- the flood line 31 according to FIG. 1 is enlarged Scale shown. Inside the receptacle 28 the flood line 31 with the temperature-dependent opening closure element 15, which has a clip closure 16, locked. Between the support structure 36 and the collecting container 28 is the flood line 31 with a compensator 29 surrounded, which on the receptacle 28 in a ball sealing seat 39 lies tight.
- FIG 4 shows the temperature-dependent on an enlarged scale opening closure element 15 according to FIG 3.
- the bow closure 16 presses a cover 40 firmly into a via a bracket 42 Ball sealing seat 39 of the flood line 31.
- the bracket 42 is over a clamping screw 17, which has a melting bolt 43, firmly connected to the flood line 31.
- the melting bolt 43 consists of silver with a melting temperature of about 960 ° C. Is between the melting bolt 43 and the cover 40 parallel to the flood line 31 a splash guard 41 for protection the melting bolt 43 is arranged against escaping cooling water 7. This means that even if there is a leak Ball sealing seat 39 ensures that melting through the melting bolt 43 not by evaporating cooling water 7 is delayed.
- FIG 5 shows an alternative embodiment of a temperature-dependent opening closure element 15 for the flood line 31 shown.
- the closure element 15 has a closure cap 18, which comprise the flood line 31 Silver strips 46 on two solder tapes 45 with the flood line 31 is soldered. Between the silver lining 46 and the abutting parts of the flood line 31 and the Cap 18 is insulation 47 from an air cushion brought in. With high heat development in the containment room 2 melt the solder tapes 45 and possibly the silver strip 46 so that the cap 18 falls off and the Flood line 31 opens.
- the shown in FIG 4 and FIG 5 Closure elements 15 each have only one melting one Element 43.46. This creates an uneven risk Melting two of the closure elements closing melting elements with the possibility of a late Avoid opening the closure element.
- the invention is characterized by a cooling system with a Cooling line and / or a flood line for cooling one to absorb meltdown designed retention space, the cooling means a passive closure element is triggered.
- the closure element opens depending on the level of the Cooling water in a flood tank so that cooling water in the Retention space or flows along its outer surfaces.
- the Closure element is a floating body, which closes the cooling line due to its buoyancy.
- Of the Float is preferably designed so that a filling pipe Reaching a level of the cooling water, which over an operational level, the float with Cooling water is filled and the cooling line opens into the Flood tank descends.
- the cooling system can have a Recirculation that is above the cooling water in the retention room feeding fluid line is guided. By repatriation and the fluid line forms a natural circulation of the Cooling water out, which effectively cools the retention space and the meltdown captured in it is.
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
- FIG 1
- ein Ausschnitt eines Längsschnittes durch eine Kernkraftanlage,
- FIG 2
- eine vergrößerte Darstellung des Verschlußelementes in der Rückführung,
- FIG 3
- eine vergrößerte Darstellung einer von dem Flutbehälter in den Auffangbehälter führenden Flutleitung,
- FIG 4
- eine vergrößerte Darstellung des Verschlußelementes der Flutleitung in dem Auffangbehälter und
- FIG 5
- eine alternative Ausführungsform des Verschlußelementes der Flutleitung in dem Auffangbehälter.
Claims (12)
- Kühlsystem (1) zur Kühlung eines der Aufnahme von Kernschmelze eines Reaktorkerns (4) einer Kernkraftanlage dienenden Rückhalteraums (2) mit einer Kühlleitung (6) und/oder einer Flutleitung (31)
dadurch gekennzeichnet, daß die Kühlleitung (6) und/oder die Flutleitung (31) von einem mit Kühlfluid (7) füllbaren Flutbehälter (8) zu dem bzw. in den Rückhalteraum (2) führt und in dem Flutbehälter (8) ein passiv öffnendes Verschlußelement (9) aufweist, das ein die Kühlleitung (6) / Flutleitung (31) abschließender Schwimmkörper (10) ist, und in Abhängigkeit von dem Pegelstand des Kühlfluids (7) schließt und öffnet. - Kühlsystem (1) nach Anspruch 1, bei dem der Schwimmkörper (10) einen mit Kühlfluid (7) füllbaren Innenraum (11) hat, in den ein Füllrohr (12) hineingeführt ist, welches eine Einlaßöffnung (13) für Kühlfluid (7) hat, durch die bei einem einen betrieblichen Pegelstand (14) übersteigenden Flutpegelstand (32) das Kühlfluid (7) einströmt.
- Kühlsystem (1) nach einem der Ansprüche 1 oder 2, bei dem der Schwimmkörper (10) eine Kondenswasser-Absaugung (19) aufweist.
- Kühlsystem (1) nach einem der Ansprüche 1 bis 3, mit einer geodätisch oberhalb der Kühlleitung (6) / Flutleitung (31) verlaufenden Rückführung (20) für Kühlfluid (7), welche den Rückhalteraum (2) mit dem Flutbehälter (8) verbindet und in dem Flutbehälter (8) ein weiteres pegelstandabhängig öffnendes Verschlußelement (21) aufweist.
- Kühlsystem (1) nach Anspruch 4, bei dem das weitere Verschlußelement (21) ein Kugelventil (22) aufweist.
- Kühlsystem (1) nach einem der Ansprüche 1 bis 5, bei dem die Flutleitung (31) in dem Rückhalteraum (2) mit einem temperaturabhängig öffnenden Verschlußelement (15) verschlossen ist.
- Kühlsystem (1) nach Anspruch 6, bei dem das temperaturabhängig öffnende Verschlußelement (15) ein Bügelverschluß (16) mit einer oberhalb von 900 °C aufschmelzenden Spannschraube (17) aus Silber ist.
- Kühlsystem (1) nach Anspruch 6, bei dem das temperaturabhängig öffnende Verschlußelement (15) eine mit Silber verlötete Verschlußkappe (18) ist.
- Kühlsystem (1) nach einem der Ansprüche 1 bis 8, welches eine Außenkühlung (23) zur Kühlung zumindest eines Bodens (24) und/oder einer Wand (25) des Rückhalteraums (2) mit Kühlfluid (7) hat, wobei die Kühlleitung (6) den Flutbehälter (8) mit der Außenkühlung (23) verbindet.
- Kühlsystem (1) nach einem der Ansprüche 1 bis 9, bei dem der Rückhalteraum (2) ein tiegelartiger, unterhalb des Reaktorkerns (4) angeordneter Auffangbehälter (28) ist.
- Kühlsystem (1) nach Anspruch 10, bei dem die Flutleitung(31) außerhalb des Auffangbehälters (28) einen Kompensator (29) zur Kompensation von Wärmedehnungen des Auffangbehälters (28) aufweist.
- Kühlsystem (1) nach einem der Ansprüche 1 bis 9, bei dem der Rückhalteraum (2) ein seitlich unterhalb des Reaktorkerns (4) angeordneter Ausbreitungsraum ist.
Applications Claiming Priority (3)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE4446421A DE4446421C2 (de) | 1994-12-23 | 1994-12-23 | Kühlsystem zur Kühlung eines zur Aufnahme von Kernschmelze ausgelegten Rückhalteraums |
DE4446421 | 1994-12-23 | ||
PCT/DE1995/001823 WO1996020485A1 (de) | 1994-12-23 | 1995-12-20 | Kühlsystem zur kühlung eines zur aufnahme von kernschmelze ausgelegten rückhalteraums |
Publications (2)
Publication Number | Publication Date |
---|---|
EP0799485A1 EP0799485A1 (de) | 1997-10-08 |
EP0799485B1 true EP0799485B1 (de) | 1999-04-28 |
Family
ID=6536993
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
EP95943159A Expired - Lifetime EP0799485B1 (de) | 1994-12-23 | 1995-12-20 | Kühlsystem zur kühlung eines zur aufnahme von kernschmelze ausgelegten rückhalteraums |
Country Status (6)
Country | Link |
---|---|
US (1) | US5889830A (de) |
EP (1) | EP0799485B1 (de) |
JP (1) | JP3602136B2 (de) |
CN (1) | CN1166888A (de) |
DE (2) | DE4446421C2 (de) |
WO (1) | WO1996020485A1 (de) |
Families Citing this family (11)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2001510559A (ja) * | 1996-12-05 | 2001-07-31 | シーメンス アクチエンゲゼルシヤフト | 炉心溶融物を収容し拡散させるための容器並びにその容器を備えた原子力設備 |
EP1133771B1 (de) * | 1998-11-26 | 2010-10-13 | AREVA NP GmbH | Vorrichtung zum auffangen und kühlen einer schmelze |
US7558360B1 (en) * | 2003-12-31 | 2009-07-07 | General Electric Company | Core catcher cooling |
JP4612558B2 (ja) * | 2006-02-22 | 2011-01-12 | 株式会社東芝 | コアキャッチャーおよび原子炉格納容器 |
EP1988551B1 (de) | 2006-02-22 | 2015-01-28 | Kabushiki Kaisha Toshiba | Kernfaenger |
DE102006010826A1 (de) | 2006-03-07 | 2007-09-13 | Framatome Anp Gmbh | Kerntechnische Anlage sowie Verschlussvorrichtung für deren Sicherheitsbehälter |
US8401142B2 (en) * | 2007-02-20 | 2013-03-19 | Westinghouse Electric Company Llc | Nuclear reactor vessel fuel thermal insulating barrier |
US8837665B2 (en) * | 2007-08-03 | 2014-09-16 | Charles E. Ramberg | Ex-vessel accident mitigation |
JP4987681B2 (ja) * | 2007-12-12 | 2012-07-25 | 株式会社東芝 | 原子炉格納容器及び漏水検知床 |
CN105280249B (zh) * | 2015-09-16 | 2018-04-27 | 中广核工程有限公司 | 核电站反应堆压力容器与屏蔽墙的组合结构 |
CN105931680B (zh) * | 2016-06-20 | 2018-04-06 | 中广核(北京)仿真技术有限公司 | 一种堆熔物收集冷却系统 |
Family Cites Families (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH02281190A (ja) * | 1989-03-27 | 1990-11-16 | General Electric Co <Ge> | 原子炉格納構造物の安全冷却系 |
US5080857A (en) * | 1989-09-19 | 1992-01-14 | General Electric Company | Passive lower drywell flooder |
DE4041295A1 (de) * | 1990-12-21 | 1992-07-02 | Siemens Ag | Kernreaktor-anlage, insbesondere fuer leichtwasserreaktoren, mit einer kernrueckhaltevorrichtung, verfahren zur notkuehlung bei einer solchen kernreaktor-anlage und verwendung turbulenzerzeugender deltafluegel |
JPH0572372A (ja) * | 1991-09-10 | 1993-03-26 | Toshiba Corp | 原子炉の炉心デブリ冷却装置 |
JP3150451B2 (ja) * | 1992-10-20 | 2001-03-26 | 株式会社日立製作所 | 原子炉設備 |
DE4337367A1 (de) * | 1993-06-08 | 1994-12-15 | Siemens Ag | Verschlußeinrichtung zum Ingangsetzen der Kühlung für eine Kernschmelze |
-
1994
- 1994-12-23 DE DE4446421A patent/DE4446421C2/de not_active Expired - Fee Related
-
1995
- 1995-12-20 CN CN95196477A patent/CN1166888A/zh active Pending
- 1995-12-20 DE DE59505798T patent/DE59505798D1/de not_active Expired - Lifetime
- 1995-12-20 WO PCT/DE1995/001823 patent/WO1996020485A1/de not_active Application Discontinuation
- 1995-12-20 JP JP52011896A patent/JP3602136B2/ja not_active Expired - Fee Related
- 1995-12-20 EP EP95943159A patent/EP0799485B1/de not_active Expired - Lifetime
-
1997
- 1997-06-23 US US08/881,087 patent/US5889830A/en not_active Expired - Lifetime
Also Published As
Publication number | Publication date |
---|---|
CN1166888A (zh) | 1997-12-03 |
DE4446421A1 (de) | 1996-06-27 |
EP0799485A1 (de) | 1997-10-08 |
JPH10511461A (ja) | 1998-11-04 |
US5889830A (en) | 1999-03-30 |
DE59505798D1 (de) | 1999-06-02 |
DE4446421C2 (de) | 2000-05-11 |
WO1996020485A1 (de) | 1996-07-04 |
JP3602136B2 (ja) | 2004-12-15 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
EP0799485B1 (de) | Kühlsystem zur kühlung eines zur aufnahme von kernschmelze ausgelegten rückhalteraums | |
EP0174380B1 (de) | Anlage mit einem nuklearen Heizreaktor | |
DE69014794T2 (de) | Passiver Fluter für die untere trockene Sammelkammer. | |
EP0702835B1 (de) | Einrichtung und verfahren zum auffangen und kühlen von kernschmelze | |
EP0706707B1 (de) | Einrichtung zum auffangen und kühlen von kernschmelze | |
DE69209402T2 (de) | Passives Kühlsystem für flüssigmetallgekühlte Kernreaktoren mit einem Reservekühlkanal | |
EP2609597B1 (de) | Verfahren zur druckentlastung eines kernkraftwerks, druckentlastungssystem für ein kernkraftwerk sowie zugehöriges kernkraftwerk | |
DE68903787T2 (de) | Kernreaktor mit notkuehlwassereinspeiseeinrichtung. | |
DE2241303C3 (de) | Anordnung zur druckmindernden Dekontaminierungssprühung für eine Kernreaktoranlage | |
DE68925855T2 (de) | Druckwasserkernreaktor mit intrinsischer Sicherheit | |
DE4032736C2 (de) | Kühleinrichtungen im Fundamentbereich eines Kernreaktors zur Kühlung einer Kernschmelze in einem hypothetischen Störfall | |
DE1915371A1 (de) | Kernkraftanlage | |
DE69206094T2 (de) | Betonstrukturschutz- und Kühlvorrichtung eines Kernreaktores, dessen Spaltzone nach einem Unfall eine Schmelzung erfährt. | |
DE2906629A1 (de) | Vorrichtung zur lagerung sich selbst erhitzender radioaktiver materialien | |
EP0629308B1 (de) | Sicherheitseinrichtung gegen überdruckversagen eines kernreaktor-druckbehälters | |
EP0143398B1 (de) | Behälter insbesondere für radioaktive Substanzen | |
DE2361795A1 (de) | Raum zur langzeitigen und dichten lagerung von radioaktiven abfallprodukten | |
DE19846057B4 (de) | Vorrichtung zum Kühlen und zum Schutz eines Reaktordruckbehälters bei Kernschmelzunfällen | |
DE2138046C2 (de) | Druckbehälter | |
CH621845A5 (de) | ||
WO1996020486A1 (de) | Notkühleinrichtung für eine kernreaktoranlage und verfahren zur notkühlung eines reaktorkerns | |
EP0702834B1 (de) | Einrichtung zum auffangen von kernschmelze aus einem reaktordruckbehälter | |
DE3015061A1 (de) | Sonnenkollektor mit ueberhitzungsschutz | |
EP0792508B1 (de) | Ausbreitungsraum zur aufnahme eines abschmelzenden reaktorkerns sowie verfahren zur wärmeabfuhr aus dem ausbreitungsraum | |
DE3339627C2 (de) | Reaktordruckbehälter einer wassergekühlten Kernreaktoranlage |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
PUAI | Public reference made under article 153(3) epc to a published international application that has entered the european phase |
Free format text: ORIGINAL CODE: 0009012 |
|
17P | Request for examination filed |
Effective date: 19970218 |
|
AK | Designated contracting states |
Kind code of ref document: A1 Designated state(s): CH DE ES FR GB LI SE |
|
17Q | First examination report despatched |
Effective date: 19971022 |
|
GRAG | Despatch of communication of intention to grant |
Free format text: ORIGINAL CODE: EPIDOS AGRA |
|
GRAG | Despatch of communication of intention to grant |
Free format text: ORIGINAL CODE: EPIDOS AGRA |
|
GRAH | Despatch of communication of intention to grant a patent |
Free format text: ORIGINAL CODE: EPIDOS IGRA |
|
GRAH | Despatch of communication of intention to grant a patent |
Free format text: ORIGINAL CODE: EPIDOS IGRA |
|
GRAA | (expected) grant |
Free format text: ORIGINAL CODE: 0009210 |
|
AK | Designated contracting states |
Kind code of ref document: B1 Designated state(s): CH DE ES FR GB LI SE |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: GB Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT Effective date: 19990428 Ref country code: ES Free format text: THE PATENT HAS BEEN ANNULLED BY A DECISION OF A NATIONAL AUTHORITY Effective date: 19990428 |
|
REG | Reference to a national code |
Ref country code: CH Ref legal event code: EP |
|
REF | Corresponds to: |
Ref document number: 59505798 Country of ref document: DE Date of ref document: 19990602 |
|
ET | Fr: translation filed | ||
GBV | Gb: ep patent (uk) treated as always having been void in accordance with gb section 77(7)/1977 [no translation filed] |
Effective date: 19990428 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: LI Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES Effective date: 19991231 Ref country code: CH Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES Effective date: 19991231 |
|
PLBE | No opposition filed within time limit |
Free format text: ORIGINAL CODE: 0009261 |
|
STAA | Information on the status of an ep patent application or granted ep patent |
Free format text: STATUS: NO OPPOSITION FILED WITHIN TIME LIMIT |
|
26N | No opposition filed | ||
REG | Reference to a national code |
Ref country code: FR Ref legal event code: TP Ref country code: FR Ref legal event code: CD |
|
REG | Reference to a national code |
Ref country code: FR Ref legal event code: CD Ref country code: FR Ref legal event code: CA |
|
REG | Reference to a national code |
Ref country code: DE Ref legal event code: R082 Ref document number: 59505798 Country of ref document: DE Representative=s name: TERGAU & WALKENHORST PATENTANWAELTE - RECHTSAN, DE |
|
REG | Reference to a national code |
Ref country code: DE Ref legal event code: R082 Ref document number: 59505798 Country of ref document: DE Representative=s name: TERGAU & WALKENHORST PATENTANWAELTE PARTGMBB, DE Effective date: 20130618 Ref country code: DE Ref legal event code: R082 Ref document number: 59505798 Country of ref document: DE Representative=s name: TERGAU & WALKENHORST PATENTANWAELTE - RECHTSAN, DE Effective date: 20130618 Ref country code: DE Ref legal event code: R081 Ref document number: 59505798 Country of ref document: DE Owner name: AREVA GMBH, DE Free format text: FORMER OWNER: AREVA NP GMBH, 91052 ERLANGEN, DE Effective date: 20130618 |
|
PGFP | Annual fee paid to national office [announced via postgrant information from national office to epo] |
Ref country code: DE Payment date: 20131223 Year of fee payment: 19 Ref country code: SE Payment date: 20131217 Year of fee payment: 19 |
|
PGFP | Annual fee paid to national office [announced via postgrant information from national office to epo] |
Ref country code: FR Payment date: 20131213 Year of fee payment: 19 |
|
REG | Reference to a national code |
Ref country code: DE Ref legal event code: R119 Ref document number: 59505798 Country of ref document: DE |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: SE Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES Effective date: 20141221 |
|
REG | Reference to a national code |
Ref country code: SE Ref legal event code: EUG |
|
REG | Reference to a national code |
Ref country code: FR Ref legal event code: ST Effective date: 20150831 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: DE Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES Effective date: 20150701 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: FR Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES Effective date: 20141231 |